Ian Gauld Distinguished R&D Staff Contact GAULDIC@ORNL.GOV All Publications Proposed Revision of the Decay Heat Standard ANSI/ANS-5.1-2005... Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-Calvert Cliffs, Takahama, and Three Mile Island Reactors (NUREG/CR-6968, ORNL/TM-2008/071) Technical Basis for a Proposed Expansion of Regulatory Guide 3.54-Decay Heat Generation in an Independent Spent Fuel Storage Installation (NUREG/CR-6999, ORNL/TM-2007/231) Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-ARIANE and REBUS Programs (UO<sub>2</sub> Fuel) (NUREG/CR-6969, ORNL/TM-2008/072) SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions (ORNL/TM-2010/44) Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel (NUREG/CR-6972, ORNL/TM-2008/015) OrigenArp Primer: How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN (ORNL/TM-2010/43) Experiment Isotopic Data Compiled by the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel... Evaluation of PWR Isotopic Composition Data... SCALE 6 Analysis of Isotopic Assay Benchmarks for PWR Spent Fuel... SCALE Validation Experience Using an Expanded Isotopic Assay Database for Spent Nuclear Fuel Activities of the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE... Analysis of isotopic assay data from the MALIBU program... Issues in Three-Dimensional Depletion Analysis of Measured Data Near the End of a Fuel Rod... Three-dimensional depletion analysis of the axial end of a Takahama fuel rod... SCALE analysis of CLAB decay heat measurements for LWR spent fuel assemblies... SCALE Analysis of CLAB Decay Heat Measurements for LWR Spent Fuel Assemblies Overview of ORIGEN-ARP and its Applications to VVER RBMK Overview of ORIGEN-ARP and its Applications to VVER RBMK STARBUCS: A prototypic SCALE Control Module for Automated Criticality Safety Analyses Using Burnup Credit (NUREG/CR-6748, ORNL/TM-2001/33) Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Page 3 Current page 4 Key Links
Research Highlight ORNL and international collaborators deliver world-leading spent nuclear fuel database
Research Highlight Uncertainty Quantification in (α,n) Neutron Source Calculations in an Oxide Matrix
